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    • 1. 发明专利
    • 蒸気乾燥器
    • 蒸汽干燥机
    • JP2014202401A
    • 2014-10-27
    • JP2013077898
    • 2013-04-03
    • 株式会社東芝Toshiba Corp
    • TANAKA SHOICHIABURA AKINORISHIMAZU TADAAKIKINUGASA KUNIHIKOITO YO
    • F22B37/30B01D45/08G21C15/16
    • Y02E30/40
    • 【課題】全高を低くすることが可能な蒸気乾燥器を提供する。【解決手段】円筒形状を有し、鉛直方向に上昇する蒸気が内部を通過するスカート21と、スカート上に設けられ、円筒形状を有し、鉛直方向に上昇する蒸気の進行方向に沿って配置された波板3a1、3a2、3b1、3b2を所定間隔を開けて平行に複数有する蒸気乾燥器ユニット1とを備え、蒸気乾燥器ユニットにおける波板の間を鉛直方向に上昇する蒸気が通過して湿分が分離される。【選択図】図1
    • 要解决的问题:提供能够降低整体高度的蒸汽干燥机。解决方案:蒸汽干燥机单元1包括具有圆柱形状的裙部21,并且垂直方向上升的蒸汽通过该裙部21和蒸汽干燥器单元1 其设置在具有圆筒形状的裙部上,并且沿着垂直方向上升的蒸汽的行进方向布置的多个波纹板3a1,3a2,3b1和3b2平行地以预定间隔设置。 在垂直方向上升的蒸汽通过蒸汽干燥器单元的波纹板之间,以便分离湿气。
    • 5. 发明专利
    • Apparatus and method for storing fuel cask
    • 储存燃油箱的装置和方法
    • JP2005291960A
    • 2005-10-20
    • JP2004108312
    • 2004-03-31
    • Toshiba Corp株式会社東芝
    • SUGIZAKI HARUOIMAZAKI YOSHIOKOIZUMI KENZOSATO MAKOTOABURA AKINORIIDE KENICHIROHATANO SHUNICHIDOUKEN SADATAKA
    • G21C19/32G21C19/06G21F5/12G21F9/36
    • PROBLEM TO BE SOLVED: To provide a fuel cask storage apparatus and a fuel cask storage method for securing more sufficient sealing and rapidly detecting leakage from a sealed section by a lid section, when storing a fuel cask.
      SOLUTION: The fuel cask storage apparatus comprises a fuel cask 1 comprising a cask body 2 in a vertical and cylindrical shape having an open upper end section while the peripheral section and the bottom wall section are integrated, and a double lid comprising a primary lid 6a and a secondary lid 6b fitted into the upper end opening of the cask body, thus assuring the sealing of an inner stored object and filled gas. The fuel cask storage apparatus also comprises a storage trestle 14 for vertically fixing and supporting the fuel cask from the lower portion while the fuel cask is being inverted. The storage trestle comprises a a pedestal 16 fixed and arranged on the floor of a storage location; and a retention frame 17 that is provided on the pedestal and fits and retains the outer periphery surface of the lower end section of a downward cask body 2. While the fuel cask is being stored on the storage trestle, an airtight space 20 facing the upper surface side of the pedestal, the inner periphery surface side of the retention frame, and the lower surface side of the secondary lid of the fuel cask is formed.
      COPYRIGHT: (C)2006,JPO&NCIPI
    • 要解决的问题:提供一种燃料桶储存装置和燃料桶储存方法,用于在储存燃料桶时,确保更充分的密封和快速检测由密封部分的密封部分的泄漏。 解决方案:燃料桶储存装置包括一个燃料桶1,该燃料桶1包括垂直和圆柱形的桶形体2,其具有敞开的上端部分,而周边部分和底壁部分是一体的, 初级盖6a和装在该桶体的上端开口中的次盖6b,从而确保内部储存物和填充气体的密封。 燃料桶储存装置还包括用于在燃料桶倒置时从下部垂直固定和支撑燃料桶的存放支架14。 存储支架包括固定并布置在存储位置的地板上的基座16; 以及保持框架17,其设置在基座上并且配合并保持向下的桶体2的下端部的外周面。当燃料桶被存储在存放支架上时,面向上部的气密空间20 形成基座的表面侧,保持框架的内周面侧和燃料桶的副盖的下表面侧。 版权所有(C)2006,JPO&NCIPI
    • 6. 发明专利
    • Washing device for internal pump
    • 内泵清洗装置
    • JP2004191273A
    • 2004-07-08
    • JP2002361742
    • 2002-12-13
    • Toshiba Corp株式会社東芝
    • SAEKI KIYOBUMIABURA AKINORIKINUGASA KUNIHIKO
    • G21C15/243G21C19/02G21F9/28
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To provide a washing device for internal pumps which can easily and surely remove crud adhered on a stretch tube remotely during the scheduled inspection of a reactor.
      SOLUTION: For washing the inner surface of the stretch tube (23), in a state with the motor part of internal pumps (6) penetrating a lower head (1a) of a reactor pressure vessel (1) is removed from the pressure vessel and an impeller (22a) and a pump shaft (22b) are removed in the pressure vessel, the device comprises a sealing member (28) for sealing the opening end inside the stretch tube (23), a main shaft (40) inserted from the open end outside the stretch tube (23), support members (32, 34) for rotatably supporting the main shaft (40) to the shaft core of the stretch tube, motor-driven rotation brush (35) installed at the tip end of the main shaft (40) and a cleaning-main unit, containing a spray nozzle (37) supplying washing water.
      COPYRIGHT: (C)2004,JPO&NCIPI
    • 要解决的问题:提供一种用于内部泵的清洗装置,其可以在预定的反应堆检查期间容易且可靠地移除附着在拉伸管上的粗屑。 解决方案:为了洗涤拉伸管(23)的内表面,在内部泵(6)的电机部分穿过反应堆压力容器(1)的下部头部(1a)的状态下,从 压力容器和叶轮(22a)和泵轴(22b)在压力容器中移除,该装置包括用于密封拉伸管(23)内的开口端的密封构件(28),主轴(40) 从所述拉伸管(23)外侧的开口端插入用于将所述主轴(40)可旋转地支撑在所述拉伸管的轴芯上的支撑部件(32,34),安装在所述拉伸管的所述尖端的电动旋转刷 主轴(40)的端部和清洁主单元,其包含供应洗涤水的喷嘴(37)。 版权所有(C)2004,JPO&NCIPI
    • 7. 发明专利
    • Method for inspecting inside nuclear reactor
    • 检查内核反应器的方法
    • JP2013015373A
    • 2013-01-24
    • JP2011147522
    • 2011-07-01
    • Toshiba Corp株式会社東芝
    • SUZUKI ATSUSHIABURA AKINORIMATSUNAGA KEIJIKINUGASA KUNIHIKO
    • G21C17/003G21C19/02
    • PROBLEM TO BE SOLVED: To inspect inside a nuclear reactor pressure vessel without removing a shield plug, a top cover of a nuclear reactor containment vessel, and a top cover of the nuclear reactor pressure vessel, when an accident occurs in a boiling water reactor.SOLUTION: In a method for inspecting inside a nuclear reactor that inspects inside a nuclear reactor pressure vessel 6, an isolation valve 13 is placed at a pipe 12 extending from the nuclear reactor pressure vessel and penetrating through a nuclear reactor containment vessel 4, an outside valve 14 is placed at an outer side than the isolation valve from the nuclear reactor containment vessel 4, an openable/closable access opening 15 is placed at an outer side than the outside valve 14 of the pipe 12 from the nuclear reactor containment vessel 4, the access opening 15 is closed after an inspection device 16 is inserted into the pipe 12 from the access opening, then after the inspection device 16 has moved to a position between the isolation valve 13 and the outside valve 14, the outside valve 14 is closed and the isolation valve is opened, and then the inspection device 16 moves to the inside of the nuclear reactor pressure vessel 6 to inspect the inside of the nuclear reactor pressure vessel 6.
    • 要解决的问题:为了在核反应堆压力容器内进行检查,而不用去除屏蔽塞,核反应堆安全壳的顶盖和核反应堆压力容器的顶盖,当在沸腾中发生事故时 水反应堆。 解决方案:在用于在核反应堆压力容器6内进行检查的核反应堆内进行检查的方法中,隔离阀13放置在从核反应堆压力容器延伸并穿过核反应堆安全壳4的管12处 外侧阀14被设置在与核反应堆容纳箱4的隔离阀的外侧的位置处,可开闭的进出口15位于比管11的外侧阀14的外侧更远离核反应堆的容纳 容器4在检查装置16从进入口插入管12中之后关闭进入口15,然后在检查装置16移动到隔离阀13与外侧阀14之间的位置之后, 14关闭,隔离阀打开,然后检查装置16移动到核反应堆压力容器6的内部,以检查核反应堆压机 ure船6.版权所有(C)2013,JPO&INPIT
    • 8. 发明专利
    • Method for suppressing generation of stress corrosion cracking
    • 抑制应力腐蚀开裂产生的方法
    • JP2010000543A
    • 2010-01-07
    • JP2009230668
    • 2009-10-02
    • Toshiba Corp株式会社東芝
    • SUMIYA RIETAKAHASHI HIDENORIABURA AKINORISENDA ITARU
    • B23K31/00C21D1/09C21D1/30C21D1/42C21D7/06C21D9/08C21D9/50
    • Y02P10/253
    • PROBLEM TO BE SOLVED: To provide a method for suppressing the generation of stress corrosion cracking which improves the factor of stress corrosion cracking generation for improving the stress corrosion cracking resistance of piping and allowing the piping to withstand over a long period, and improves stress corrosion cracking resistance.
      SOLUTION: In the method where the face 5 to be operated including a weld zone 3 and a weld heat-affected zone 4 in a pipe 1 is subjected to heating treatment based on prescribed heating treatment conditions, so as to suppress the generation of the stress corrosion cracking of the piping, as the heating treatment conditions, the heat input volume per unit length of the pipe 1 and/or the operating range in the piping is decided in accordance with the thickness of the pipe 1, and further, the residual stress in the back face of the face 5 to be operated to which the heat treatment is performed is improved by the heating treatment.
      COPYRIGHT: (C)2010,JPO&INPIT
    • 要解决的问题:提供一种抑制应力腐蚀开裂产生的方法,其提高应力腐蚀裂纹产生的因素,以改善管道的应力腐蚀开裂性并允许管道长时间承受,并且 提高应力腐蚀开裂性。 解决方案:在管道1中包括焊接区域3和焊接热影响区域4的操作面5基于规定的加热处理条件进行加热处理的方法中,以抑制发生 的管道的应力腐蚀开裂,作为加热处理条件,管1的单位长度的热输入量和/或管道的工作范围根据管1的厚度来决定, 通过加热处理提高了进行热处理的要操作的面5的背面中的残余应力。 版权所有(C)2010,JPO&INPIT
    • 9. 发明专利
    • Work trestle inside nuclear reactor
    • 核反应堆内的工作目标
    • JP2007178334A
    • 2007-07-12
    • JP2005378714
    • 2005-12-28
    • Toshiba Corp株式会社東芝
    • HATAKE HARUHIKOHIROSE KINZOYAMAGUCHI OSAMUSUDO KAZUOYASUDA TOSHIHIROABURA AKINORIUENO KENICHI
    • G21C19/02
    • PROBLEM TO BE SOLVED: To efficiently restore an original jet pump structure not depending solely on remote operation without causing the problem related to exposure when jet pumps are replaced.
      SOLUTION: Working floors 3, 4, 5, 6 are arranged, inside a nuclear reactor pressure vessel, on the reactor bottom section, a recirculation nozzle section of the jet pump and a riser brace section and above the jet pump. The uppermost working floor 6 arranged above the jet pump is provided with a plurality of segments divided circumferentially and capable of being opened and closed, and can be opened circumferentially in an arbitrary direction. The working floor 5 disposed in the riser brace is provided with a rotary table 25 capable of being turned around the circumference of a column and a rotary drive mechanism 26 for driving the rotary table.
      COPYRIGHT: (C)2007,JPO&INPIT
    • 要解决的问题:为了有效地恢复原始喷射泵结构,而不是仅仅依赖于远程操作,而不会在喷射泵更换时引起与曝光有关的问题。 解决方案:工作层3,4,5,6在反应堆底部的核反应堆压力容器内部,喷射泵的再循环喷嘴部分和提升管支架部分以及喷射泵上方布置。 布置在喷射泵上方的最上层的工作台面6设置有沿圆周方向分割并能够打开和关闭的多个段,并且可沿任意方向周向地开放。 设置在立管支架中的工作台5设置有能够绕柱的圆周转动的旋转台25和用于驱动旋转台的旋转驱动机构26。 版权所有(C)2007,JPO&INPIT
    • 10. 发明专利
    • Method for inspecting inside nuclear reactor
    • 检查内核反应器的方法
    • JP2013015374A
    • 2013-01-24
    • JP2011147523
    • 2011-07-01
    • Toshiba Corp株式会社東芝
    • SUZUKI ATSUSHIABURA AKINORIMATSUNAGA KEIJIKINUGASA KUNIHIKO
    • G21C17/003G21C19/02
    • PROBLEM TO BE SOLVED: To inspect inside a nuclear reactor pressure vessel without removing a shield plug for closing a nuclear reactor well, a top cover of a nuclear reactor containment vessel, and a top cover of the nuclear reactor pressure vessel, when an accident occurs in a boiling water reactor.SOLUTION: A method for inspecting inside a nuclear reactor inspects inside of a nuclear reactor pressure vessel 6 placed inside of a nuclear reactor containment vessel 4 in a boiling water reactor, where a shield plug 5 for closing a nuclear reactor well 3, a top cover 4A of a nuclear reactor containment vessel, and a top cover 6A of the nuclear reactor pressure vessel are sequentially arranged downwardly in a vertical direction. In the method, first, access holes 20, 21 are sequentially processed in the shield plug 5 and the top cover 4A of the nuclear reactor containment vessel 4 using a processing device 16, next, a head nozzle 11 arranged on the nuclear reactor pressure vessel 6 is opened by remote control, and then, an inspection device is moved inside the nuclear reactor pressure vessel 6 through the access holes 20, 21 and the head nozzle 11 to inspect inside the nuclear reactor containment vessel.
    • 要解决的问题:为了在核反应堆压力容器内部进行检查,而不用去除用于关闭核反应堆的屏蔽塞,核反应堆安全壳的顶盖和核反应堆压力容器的顶盖,当 在沸水反应堆中发生事故。 解决方案:核反应堆内的检查方法在沸水反应堆内检查放置在核反应堆安全壳4内的核反应堆压力容器6的内部,其中用于封闭核反应堆3的屏蔽塞5, 核反应堆安全壳的顶盖4A和核反应堆压力容器的顶盖6A沿垂直方向依次排列。 在该方法中,首先,使用处理装置16在保护塞5和核反应堆安全壳4的顶盖4A中依次处理进入孔20,21,接下来,设置在核反应堆压力容器 6通过遥控器打开,然后检查装置通过进入孔20,21和头喷嘴11在核反应堆压力容器6内移动,以检查核反应堆安全壳内部。 版权所有(C)2013,JPO&INPIT